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OPERATING EXPERIENCEWITH NUCLEAR POWER STATIONS

IN MEMBER STATES IN 2004

The Agencys Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United NationsHeadquarters, New York; it entered into force on 29 July 1957. The Headquarters of the Agency are situated in Vienna. Its principal objec-tive is to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world.

IAEA, 2005Permission to reproduce or translate the information contained in this publication may be obtained by writing to the International

Atomic Energy Agency, Wagramer Strasse 5, P.O. Box 100, A-1400 Vienna, Austria.Printed by the IAEA in Austria

November 2005

The following States are Members of the International Atomic Energy Agency:

AFGHANISTANALBANIAALGERIAANGOLAARGENTINAARMENIAAUSTRALIAAUSTRIAAZERBAIJANBANGLADESHBELARUSBELGIUMBENINBOLIVIABOSNIA AND HERZEGOVINABOTSWANABRAZILBULGARIABURKINA FASOCAMEROONCANADACENTRAL AFRICANREPUBLICCHILECHINACOLOMBIACOSTA RICACTE DIVOIRECROATIACUBACYPRUSCZECH REPUBLICDEMOCRATIC REPUBLIC

OF THE CONGODENMARKDOMINICAN REPUBLICECUADOREGYPTEL SALVADORERITREAESTONIAETHIOPIAFINLANDFRANCEGABONGEORGIAGERMANYGHANAGREECE

GUATEMALAHAITIHOLY SEEHONDURASHUNGARYICELANDINDIAINDONESIAIRAN, ISLAMIC REPUBLIC OFIRAQIRELANDISRAELITALYJAMAICAJAPANJORDANKAZAKHSTANKENYAKOREA, REPUBLIC OFKUWAITKYRGYZSTANLATVIALEBANONLIBERIALIBYAN ARAB JAMAHIRIYALIECHTENSTEINLITHUANIALUXEMBOURGMADAGASCARMALAYSIAMALIMALTAMARSHALL ISLANDSMAURITANIAMAURITIUSMEXICOMONACOMONGOLIAMOROCCOMYANMARNAMIBIANETHERLANDSNEW ZEALANDNICARAGUANIGERNIGERIANORWAYPAKISTANPANAMA

PARAGUAYPERUPHILIPPINESPOLANDPORTUGALQATARREPUBLIC OF MOLDOVAROMANIARUSSIAN FEDERATIONSAUDI ARABIASENEGALSERBIA AND MONTENEGROSEYCHELLESSIERRA LEONESINGAPORESLOVAKIASLOVENIASOUTH AFRICASPAINSRI LANKASUDANSWEDENSWITZERLANDSYRIAN ARAB REPUBLICTAJIKISTANTHAILANDTHE FORMER YUGOSLAV

REPUBLIC OF MACEDONIATUNISIATURKEYUGANDAUKRAINEUNITED ARAB EMIRATESUNITED KINGDOM OFGREAT BRITAIN ANDNORTHERN IRELANDUNITED REPUBLICOF TANZANIAUNITED STATES OF AMERICAURUGUAYUZBEKISTANVENEZUELAVIETNAMYEMENZAMBIAZIMBABWE

OPERATING EXPERIENCEWITH NUCLEAR POWER STATIONS

IN MEMBER STATES IN 2004

INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 2005

OPERATING EXPERIENCE WITH NUCLEAR POWER STATIONSIN MEMBER STATES IN 2004

IAEA, VIENNA, 2005STI/PUB/1237

ISBN 92-0-114305-2ISSN 1011-2634

FOREWORD This report is the thirty-sixth in the Agency's series of annual reports

on operating experience with nuclear power stations in Member States. As in previous years, in addition to annual performance data and

outage information, the report contains a historical summary of performance and outages during the lifetime of individual plants and five figures illustrating worldwide performance and statistical data.

It is hoped that this report and related Agency publications will be

useful to everyone concerned with nuclear power reactors. Suggestions and corrections from readers would be most welcome.

Director Division of Nuclear Power International Atomic Energy Agency Wagramer Strasse 5, P. O. Box 100 A-1400 Vienna, Austria

CONTENTS

1. Introduction ................................................................................................. 9 2. Nuclear power station units in Member States ............................................ 11 3. Definitions ................................................................................................... 19 4. Figures ...................................................................................................... 27 5. Abbreviations .............................................................................................. 31 6. Data sheets on individual nuclear power station units ............................... 35 7. Non-electrical application of nuclear energy in Member States ................. 877

1. INTRODUCTION

This report is the thirty-sixth in the Agency's series of annual reports on operating experience with nuclear power stations in Member States.

The report is a direct output from the Agency's Power Reactor Information System (PRIS), whose databank contains all operating experience data published in the Agency's operating experience annual reports since 1971 and basic information on power reactors, including design data. It presents operating experience data for all worldwide nuclear power plants after starting commercial operation. The PRIS databank is available free of charge to IAEA Member States through its two services: PRIS-PC, and PRIS CD-ROM. The PRIS-PC allows direct access to the database through the Internet. The PRIS-PC on CD-ROM only includes data for reactors in operation, under construction and shutdown. It keeps the same feature as in the current front-end-tool PRIS-PC interface. This front-end-tool interface allows to search and query through pre-designed statistics. The PRIS-PC on CD-ROM contains mapping interface including a view of the world map with zooming features to country, region and site map and links to PRIS database to retrieve related (nuclear power plant) information. PRIS data and related indicators are also available on the PRIS Website: www.iaea.org/programmes/a2. It contains publicly available information about reactor units and nuclear industry results.

Load, operation and availability factors are used as the basic performance indicators. Energy unavailability factors, separate for planned and unplanned unavailability, due either to causes under plant management control or external causes out of plant management control, are used as a measure of energy lost through a unit not being available. However, some ambiguity remains in the operators' reports of the unavailability data, resulting in inconsistencies in these factors. It is recognized that there is an inherent difficulty in reporting unavailability in energy due to external causes with relation to energy losses due to load following operation and grid limitation. It should be noted that, for load, operation and unavailability factors, there might be differences between the data of this report and those published elsewhere. To avoid confusion, reference should be made to the definitions given in Section 3. In Section 4 this report presents figures illustrating worldwide performance indicators up to 2004.

According to the information available to the Agency at the end of 2004, there were 440 nuclear power reactors operating in the world, with a total net capacity of 366.3 GW(e).

Five new reactor units were connected to the grid in 2004 (two in Ukraine and one each in China, Japan and the Russian Federation), and one laid-up plant was reconnected in Canada. This compares to two new grid connections and and two reconnections in 2003.

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There were five NPP retirements in 2004 four 50 MW(e) units in the United Kingdom and the 1185 MW(e) Ignalina-1 reactor in Lithuania. This compares to six retirements in 2003.

At the end of 2004 here were 26 nuclear power plants under construction in the world with a total net capacity 20.8 GW(e). Construction began on two NPPs in 2004, Indias 500 MW(e) prototype fast breeder reactor and Japans 866 MW(e) Tomari-3 PWR. In addition, active construction resumed on two NPPs in the Russian Federation, Kalinin-4 and Balakovo-5.

The information contained in the report was made available to the Agency through designated national correspondents and the US Nuclear Regulatory Commission (NRC) and Department of Energy (DOE).

The Agency appreciates the valuable assistance that it has obtained from the national authorities, official correspondents and various electrical utilities in gathering the information for this report.

This publication includes information received by the Agency up to 30 September 2004. Up to this date from 15 British units (operated by British Energy) and from 1 French unit (Phenix) had not been reported. Information received after that date, although not included in this publication, is available in the PRIS database.

The report was compiled by staff of the Agency's Division of Nuclear Power. It is hoped that it will be useful to nuclear power plant operators, nuclear system designers, nuclear power planners, interested professional engineers and scientists and others concerned with the operating experience with nuclear power reactors. Suggestions and corrections from readers would be most welcome.

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Country Name Reactor Code Reactor Name Page

ARGENTINA AR1 ATUCHA-1 37AR2 EMBALSE 39

ARMENIA AM19 ARMENIA-2 41

BELGIUM BE2 DOEL-1 43BE4 DOEL-2 45BE5 DOEL-3 47BE7 DOEL-4 49BE3 TIHANGE-1 51BE6 TIHANGE-2 53BE8 TIHANGE-3 55

BRAZIL BR1 ANGRA-1 57BR2 ANGRA-2 59

BULGARIA BG3 KOZLODUY-3 61BG4 KOZLODUY-4 63BG5 KOZLODUY-5 65BG6 KOZLODUY-6 67

CANADA CA10 BRUCE-3 69CA11 BRUCE-4 71CA18 BRUCE-5 73CA19 BRUCE-6 75CA20 BRUCE-7 77CA21 BRUCE-8 79CA22 DARLINGTON-1 81CA23 DARLINGTON-2 83CA24 DARLINGTON-3 85CA25 DARLINGTON-4 87CA12 GENTILLY-2 89CA4 PICKERING-1CA7 PICKERING-4 91CA13 PICKERING-5 93CA14 PICKERING-6 95CA15 PICKERING-7 97CA16 PICKERING-8 99CA17 POINT LEPREAU 101

CHINA CN2 GUANGDONG-1 103CN3 GUANGDONG-2 105CN6 LINGAO 1 107CN7 LINGAO 2 109CN1 QINSHAN 1 111CN4 QINSHAN 2 - 1 113CN5 QINSHAN 2 - 2 115CN8 QINSHAN 3 - 1 117CN9 QINSHAN 3 - 2 119

(Including TAIWAN, CHINA) TW1 CHIN SHAN-1 121TW2 CHIN SHAN-2 123TW3 KUOSHENG-1 125TW4 KUOSHENG-2 127TW5 MAANSHAN-1 129TW6 MAANSHAN-2 131

2. NUCLEAR POWER STATION UNITS IN MEMBER STATES(as of January 2005)

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CZECH REPUBLIC CZ4 DUKOVANY-1 133CZ5 DUKOVANY-2 135CZ8 DUKOVANY-3 137CZ9 DUKOVANY-4 139CZ23 TEMELIN-1 141CZ24 TEMELIN-2 143

FINLAND FI1 LOVIISA-1 145FI2 LOVIISA-2 147FI3 OLKILUOTO-1 149FI4 OLKILUOTO-2 151

FRANCE FR54 BELLEVILLE-1 153FR55 BELLEVILLE-2 155FR32 BLAYAIS-1 157FR33 BLAYAIS-2 159FR34 BLAYAIS-3 161FR35 BLAYAIS-4 163FR13 BUGEY-2 165FR14 BUGEY-3 167FR15 BUGEY-4 169FR16 BUGEY-5 171FR50 CATTENOM-1 173FR53 CATTENOM-2 175FR60 CATTENOM-3 177FR65 CATTENOM-4 179FR40 CHINON-B-1 181FR41 CHINON-B-2 183FR56 CHINON-B-3 185FR57 CHINON-B-4 187FR62 CHOOZ-B-1 189FR70 CHOOZ-B-2 191FR72 CIVAUX-1 193FR73 CIVAUX-2 195FR42 CRUAS-1 197FR43 CRUAS-2 199FR44 CRUAS-3 201FR45 CRUAS-4 203FR22 DAMPIERRE-1 205FR29 DAMPIERRE-2 207FR30 DAMPIERRE-3 209FR31 DAMPIERRE-4 211FR11 FESSENHEIM-1 213FR12 FESSENHEIM-2 215FR46 FLAMANVILLE-1 217FR47 FLAMANVILLE-2 219FR61 GOLFECH-1 221FR68 GOLFECH-2 223FR20 GRAVELINES-1 225FR21 GRAVELINES-2 227FR27 GRAVELINES-3 229FR28 GRAVELINES-4 231FR51 GRAVELINES-5 233FR52 GRAVELINES-6 235FR58 NOGENT-1 237FR59 NOGENT-2 239FR36 PALUEL-1 241FR37 PALUEL-2 243

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FRANCE FR38 PALUEL-3 245FR39 PALUEL-4 247FR63 PENLY-1 249FR64 PENLY-2 251FR10 PHENIXFR48 ST. ALBAN-1 253FR49 ST. ALBAN-2 255FR17 ST. LAURENT-B-1 257FR23 ST. LAURENT-B-2 259FR18 TRICASTIN-1 261FR19 TRICASTIN-2 263FR25 TRICASTIN-3 265FR26 TRICASTIN-4 267

GERMANY DE12 BIBLIS-A (KWB A) 269DE18 BIBLIS-B (KWB B) 271DE32 BROKDORF (KBR) 273DE13 BRUNSBUETTEL (KKB) 275DE33 EMSLAND (KKE) 277DE23 GRAFENRHEINFELD (KKG) 279DE27 GROHNDE (KWG) 281DE26 GUNDREMMINGEN-B (GUN-B) 283DE28 GUNDREMMINGEN-C (GUN-C) 285DE16 ISAR-1 (KKI 1) 287DE31 ISAR-2 (KKI 2) 289DE20 KRUEMMEL (KKK) 291DE15 NECKARWESTHEIM-1 (GKN 1) 293DE44 NECKARWESTHEIM-2 (GKN 2) 295DE5 OBRIGHEIM (KWO) 297DE14 PHILIPPSBURG-1 (KKP 1) 299DE24 PHILIPPSBURG-2 (KKP 2) 301DE17 UNTERWESER (KKU) 303

HUNGARY HU1 PAKS-1 305HU2 PAKS-2 307HU3 PAKS-3 309HU4 PAKS-4 311

INDIA IN13 KAIGA-1 313IN14 KAIGA-2 315IN9 KAKRAPAR-1 317IN10 KAKRAPAR-2 319IN5 MADRAS-1 321IN6 MADRAS-2 323IN7 NARORA-1 325IN8 NARORA-2 327IN3 RAJASTHAN-1 329IN4 RAJASTHAN-2 331IN11 RAJASTHAN-3 333IN12 RAJASTHAN-4 335IN1 TARAPUR-1 337IN2 TARAPUR-2 339

JAPAN JP5 FUKUSHIMA-DAIICHI-1 341JP9 FUKUSHIMA-DAIICHI-2 343JP10 FUKUSHIMA-DAIICHI-3 345JP16 FUKUSHIMA-DAIICHI-4 347JP17 FUKUSHIMA-DAIICHI-5 349JP18 FUKUSHIMA-DAIICHI-6 351JP25 FUKUSHIMA-DAINI-1 353

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JAPAN JP26 FUKUSHIMA-DAINI-2 355JP35 FUKUSHIMA-DAINI-3 357JP38 FUKUSHIMA-DAINI-4 359JP12 GENKAI-1 361JP27 GENKAI-2 363JP45 GENKAI-3 365JP46 GENKAI-4 367JP11 HAMAOKA-1 369JP24 HAMAOKA-2 371JP36 HAMAOKA-3 373JP49 HAMAOKA-4 375JP23 IKATA-1 377JP32 IKATA-2 379JP47 IKATA-3 381JP33 KASHIWAZAKI KARIWA-1 383JP39 KASHIWAZAKI KARIWA-2 385JP52 KASHIWAZAKI KARIWA-3 387JP53 KASHIWAZAKI KARIWA-4 389JP40 KASHIWAZAKI KARIWA-5 391JP55 KASHIWAZAKI KARIWA-6 393JP56 KASHIWAZAKI KARIWA-7 395JP4 MIHAMA-1 397JP6 MIHAMA-2 399JP14 MIHAMA-3 401JP15 OHI-1 403JP19 OHI-2 405JP50 OHI-3 407JP51 OHI-4 409JP22 ONAGAWA-1 411JP54 ONAGAWA-2 413JP57 ONAGAWA-3 415JP28 SENDAI-1 417JP37 SENDAI-2 419JP48 SHIKA-1 421JP7 SHIMANE-1 423JP41 SHIMANE-2 425JP8 TAKAHAMA-1 427JP13 TAKAHAMA-2 429JP29 TAKAHAMA-3 431JP30 TAKAHAMA-4 433JP21 TOKAI-2 435JP43 TOMARI-1 437JP44 TOMARI-2 439JP3 TSURUGA-1 441JP34 TSURUGA-2 443

KOREA, REPUBLIC OF KR1 KORI-1 445KR2 KORI-2 447KR5 KORI-3 449KR6 KORI-4 451KR9 ULCHIN-1 453KR10 ULCHIN-2 455KR13 ULCHIN-3 457KR14 ULCHIN-4 459KR19 ULCHIN-5 461KR3 WOLSONG-1 463KR4 WOLSONG-2 465KR15 WOLSONG-3 467KR16 WOLSONG-4 469

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KOREA, REPUBLIC OF KR7 YONGGWANG-1 471KR8 YONGGWANG-2 473KR11 YONGGWANG-3 475KR12 YONGGWANG-4 477KR17 YONGGWANG-5 479KR18 YONGGWANG-6 481

LITHUANIA, REPUBLIC OF LT46 IGNALINA-1 483LT47 IGNALINA-2 485

MEXICO MX1 LAGUNA VERDE-1 487MX2 LAGUNA VERDE-2 489

NETHERLANDS NL2 BORSSELE 491

PAKISTAN PK2 CHASNUPP 1 493PK1 KANUPP 495

ROMANIA RO1 CERNAVODA-1 497

RUSSIAN FEDERATION RU96 BALAKOVO-1 499RU97 BALAKOVO-2 501RU98 BALAKOVO-3 503RU99 BALAKOVO-4 505RU21 BELOYARSKY-3(BN-600) 507RU141 BILIBINO-1 509RU142 BILIBINO-2 511RU143 BILIBINO-3 513RU144 BILIBINO-4 515RU30 KALININ-1 517RU31 KALININ-2 519RU12 KOLA-1 521RU13 KOLA-2 523RU32 KOLA-3 525RU33 KOLA-4 527RU17 KURSK-1 529RU22 KURSK-2 531RU38 KURSK-3 533RU39 KURSK-4 535RU15 LENINGRAD-1 537RU16 LENINGRAD-2 539RU34 LENINGRAD-3 541RU35 LENINGRAD-4 543RU9 NOVOVORONEZH-3 545RU11 NOVOVORONEZH-4 547RU20 NOVOVORONEZH-5 549RU23 SMOLENSK-1 551RU24 SMOLENSK-2 553RU67 SMOLENSK-3 555RU59 VOLGODONSK-1 557

SLOVAK REPUBLIC SK2 BOHUNICE-1 559SK3 BOHUNICE-2 561SK13 BOHUNICE-3 563SK14 BOHUNICE-4 565SK6 MOCHOVCE-1 567SK7 MOCHOVCE-2 569

SLOVENIA SI1 KRSKO 571

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SOUTH AFRICA ZA1 KOEBERG-1 573ZA2 KOEBERG-2 575

SPAIN ES6 ALMARAZ-1 577ES7 ALMARAZ-2 579ES8 ASCO-1 581ES9 ASCO-2 583ES10 COFRENTES 585ES1 JOSE CABRERA-1(ZORITA) 587ES2 SANTA MARIA DE GARONA 589ES11 TRILLO-1 591ES16 VANDELLOS-2 593

SWEDEN SE8 BARSEBACK-2 595SE9 FORSMARK-1 597SE11 FORSMARK-2 599SE14 FORSMARK-3 601SE2 OSKARSHAMN-1 603SE3 OSKARSHAMN-2 605SE12 OSKARSHAMN-3 607SE4 RINGHALS-1 609SE5 RINGHALS-2 611SE7 RINGHALS-3 613SE10 RINGHALS-4 615

SWITZERLAND CH1 BEZNAU-1 617CH3 BEZNAU-2 619CH4 GOESGEN 621CH5 LEIBSTADT 623CH2 MUEHLEBERG 625

UKRAINE UA40 KHMELNITSKI-1 627UA27 ROVNO-1 629UA28 ROVNO-2 631UA29 ROVNO-3 633UA44 SOUTH UKRAINE-1 635UA45 SOUTH UKRAINE-2 637UA48 SOUTH UKRAINE-3 639UA54 ZAPOROZHE-1 641UA56 ZAPOROZHE-2 643UA78 ZAPOROZHE-3 645UA79 ZAPOROZHE-4 647UA126 ZAPOROZHE-5 649UA127 ZAPOROZHE-6 651

UNITED KINGDOM GB2A CHAPELCROSS 1GB2B CHAPELCROSS 2GB2C CHAPELCROSS 3GB2D CHAPELCROSS 4GB9A DUNGENESS-A1 653GB9B DUNGENESS-A2 655GB18A DUNGENESS-B1GB18B DUNGENESS-B2GB19A HARTLEPOOL-A1GB19B HARTLEPOOL-A2GB20A HEYSHAM-A1GB20B HEYSHAM-A2GB22A HEYSHAM-B1GB22B HEYSHAM-B2GB16A HINKLEY POINT-B1

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UNITED KINGDOM GB16B HINKLEY POINT-B2GB17A HUNTERSTON-B1GB17B HUNTERSTON-B2GB11A OLDBURY-A1 657GB11B OLDBURY-A2 659GB10A SIZEWELL-A1 661GB10B SIZEWELL-A2 663GB24 SIZEWELL-BGB23A TORNESS 1GB23B TORNESS 2GB13A WYLFA 1 665GB13B WYLFA 2 667

UNITED STATES OF AMERICA US313 ARKANSAS ONE-1 669US368 ARKANSAS ONE-2 671US334 BEAVER VALLEY-1 673US412 BEAVER VALLEY-2 675US456 BRAIDWOOD-1 677US457 BRAIDWOOD-2 679US259 BROWNS FERRY-1 681US260 BROWNS FERRY-2 683US296 BROWNS FERRY-3 685US325 BRUNSWICK-1 687US324 BRUNSWICK-2 689US454 BYRON-1 691US455 BYRON-2 693US483 CALLAWAY-1 695US317 CALVERT CLIFFS-1 697US318 CALVERT CLIFFS-2 699US413 CATAWBA-1 701US414 CATAWBA-2 703US461 CLINTON-1 705US397 COLUMBIA 707US445 COMANCHE PEAK-1 709US446 COMANCHE PEAK-2 711US298 COOPER 713US302 CRYSTAL RIVER-3 715US346 DAVIS BESSE-1 717US275 DIABLO CANYON-1 719US323 DIABLO CANYON-2 721US315 DONALD COOK-1 723US316 DONALD COOK-2 725US237 DRESDEN-2 727US249 DRESDEN-3 729US331 DUANE ARNOLD-1 731US341 ENRICO FERMI-2 733US348 FARLEY-1 735US364 FARLEY-2 737US333 FITZPATRICK 739US285 FORT CALHOUN-1 741US416 GRAND GULF-1 743US261 H.B. ROBINSON-2 745US321 HATCH-1 747US366 HATCH-2 749US354 HOPE CREEK-1 751US247 INDIAN POINT-2 753US286 INDIAN POINT-3 755US305 KEWAUNEE 757US373 LASALLE-1 759US374 LASALLE-2 761

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UNITED STATES OF AMERICA US352 LIMERICK-1 763US353 LIMERICK-2 765US369 MCGUIRE-1 767US370 MCGUIRE-2 769US336 MILLSTONE-2 771US423 MILLSTONE-3 773US263 MONTICELLO 775US220 NINE MILE POINT-1 777US410 NINE MILE POINT-2 779US338 NORTH ANNA-1 781US339 NORTH ANNA-2 783US269 OCONEE-1 785US270 OCONEE-2 787US287 OCONEE-3 789US219 OYSTER CREEK 791US255 PALISADES 793US528 PALO VERDE-1 795US529 PALO VERDE-2 797US530 PALO VERDE-3 799US277 PEACH BOTTOM-2 801US278 PEACH BOTTOM-3 803US440 PERRY-1 805US293 PILGRIM-1 807US266 POINT BEACH-1 809US301 POINT BEACH-2 811US282 PRAIRIE ISLAND-1 813US306 PRAIRIE ISLAND-2 815US254 QUAD CITIES-1 817US265 QUAD CITIES-2 819US244 R.E. GINNA 821US458 RIVER BEND-1 823US272 SALEM-1 825US311 SALEM-2 827US361 SAN ONOFRE-2 829US362 SAN ONOFRE-3 831US443 SEABROOK-1 833US327 SEQUOYAH-1 835US328 SEQUOYAH-2 837US400 SHEARON HARRIS-1 839US498 SOUTH TEXAS-1 841US499 SOUTH TEXAS-2 843US335 ST. LUCIE-1 845US389 ST. LUCIE-2 847US280 SURRY-1 849US281 SURRY-2 851US387 SUSQUEHANNA-1 853US388 SUSQUEHANNA-2 855US289 THREE MILE ISLAND-1 857US250 TURKEY POINT-3 859US251 TURKEY POINT-4 861US271 VERMONT YANKEE 863US395 VIRGIL C. SUMMER-1 865US424 VOGTLE-1 867US425 VOGTLE-2 869US382 WATERFORD-3 871US390 WATTS BAR-1 873US482 WOLF CREEK 875

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3. DEFINITIONS

1. Reference Unit Power - maximum electrical capacity, RUP [MW(e)]

The reference unit power is the maximum (electrical) power that could be maintained continuously throughout a prolonged period of operation under reference ambient conditions. It is specified that this value must remain constant for a given unit unless, following permanent modification, or a new permanent authorization, the management decides to amend the original value. The reference unit power may be gross of net:

The gross RUP (Pg, MW(e)) is deemed to be measured at the output terminals of all generator sets in the station; it includes therefore the power taken by the station auxiliaries and losses in transformers that are considered integral parts of the station. The net RUP (Pn, MW(e)), indicating the maximum power that can be supplied, is measured at the station outlet terminals, i.e. after deducting the power taken by station auxiliaries and the losses in the transformers that are considered integral parts of the station.

2. Design net capacity [MW(e)] The net reference unit power as specified in an original unit design. 3. Reference period, T [hours] For units in power ascension at the end of the period, the clock hours from the beginning of the period or the first electrical production, whichever comes last, to the end of the period. For units in commercial operation at the end of the period, the clock hours from the beginning of the period or of commercial operation, whichever comes last, to the end of the period or permanent shutdown, whichever comes first. 4. On-line hours, t [hours] The total clock hours in the reference period during which the unit operated with breakers closed to the station bus. 5. Reference Energy Generation, REG [MW(e)h] Net electrical energy which would have been produced if the unit were operated continuously at the reference unit power during the whole reference period. 6. Energy Generated (net), EG [GW(e)h] Net electrical energy produced during the reference period as measured at the unit outlet terminals, i.e. after deducting the electrical energy taken by unit auxiliaries and the losses in transformers that are considered integral parts of the unit. If this quantity is less than zero, zero is reported.

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7. Load Factor, LF [%]

100 REGEG = LF

Load factor, for a given period, is the ratio of the energy, which the power unit has produced over that period, to the energy it would have produced at its reference power capacity over that period. 8. Operation factor, OF [%]

100 Tt = OF

Operation factor is the ratio of the number of hours the unit was on-line, to the total number of hours in the reference period, expressed as a percentage. It is a measure of the unit time availability on the grid and does not depend on the operating power level. 9. Available capacity, P [MW(e)] The available capacity at a given moment is the maximum net capacity at which the unit or station is able or is authorized to be operated at a continuous rating under the prevailing conditions assuming unlimited transmission facilities. 10. Energy loss, EL [MW(e)h] Energy loss is the energy which could have been produced during the reference period by the unavailable capacity; it is categorized into three types:

- PEL - planned energy loss - UEL - unplanned energy loss - XEL - energy loss due to causes external to the plant

UEL comprise shutdowns, unplanned load reductions or outage extensions. 11. Unavailability The unit unavailability is defined as a status when the plant is not able to operate at its maximum capacity (reference power). This condition, which may be under or beyond plant management control, should only reflect lack of availability of the plant itself, regardless of energy demand, transmission grid condition or political situation in the country. Unavailability is classified as planned if it is foreseen at least 4 months in advance, generally at the time when the annual overhaul programme is established, and if the beginning of the unavailability period can be largely controlled and deferred by management. Unavailability is classified as unplanned if not scheduled at least four weeks in advance. Power plant operation at lower than maximum capacity because of lower demand from the grid but available to operate at the maximum capacity, does not constitute unavailability, either planned or unplanned. 12. Energy Availability Factor, EAF [%]

100 REG

XELUELPELREG = EAF

The energy availability factor over a specified period, is the ratio of the energy that the available capacity could have produced during this period, to the energy that the reference unit power could have produced during the same period. 13. Energy Unavailability Factor, EUF [%]

t = number of hours on-line [h] T = number of hours in the reference period [h]

EG = energy generated (net), [MW(e)h REG = reference energy generation [MW(e)h]

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100 REGEL = EUF

The unavailability factor over a specified period is the ratio of the energy losses EL that have not been produced during this period due to the unavailable capacity, to the energy that the reference unit power could have produced during the same period. The energy unavailability factor EUF over a specified period can be divided into: PUF = planned unavailability factor UUF = unplanned unavailability factor due to causes in the plant XUF = unplanned unavailability factor due to causes external to the plant. The unavailability factor can be expressed as: EUF = 100 EAF 14. Unit capability factor, UCF [%]

100 REG

UELPELREG = UCF

Unit capability factor is defined as the ratio of the energy that the unit was capable to generate over a given time period considering only limitation under the plant management control, to the reference energy generation over the same time period, expressed as a percentage. Both of these energy generation terms are determined relative to reference ambient conditions. 15. Construction start Date when first major placing of concrete, usually for the base mat of the reactor building, is done. 16. First criticality Date when the reactor is made critical for the first time. 17. Grid connection Date when the plant is first connected to the electrical grid for supply of power. 18. Commercial operation Date when the plant is handed over by the contractors to the owner and declared officially to be in commercial operation. 19. Shutdown Date when the plant is officially declared shut down by the owner and taken out of operation permanently. 20. Outages For the purpose of PRIS coding, the outage is defined as any status of a reactor unit, when its actual output power is lower than the reference unit power for a period of time. By this definition, the outage includes both power reduction and unit shutdown. The outage is considered significant, if the loss in the energy production corresponds to at least ten hours of continuous operation at the reference unit power or if it has been caused by an unplanned reactor scram (even if the unit had been shut down for less than 10 hours). 21. Outage duration [h]

21

The total clock hours of the outage measured from the beginning of the reference period or the outage, whichever comes last, to the end of the reference period or the outage, whichever comes first. 22. Factors refer to the plants which were in commercial operation during the whole of the reference period. 23. Cumulative factors are given for the plants which were in commercial operation during full calendar years. 24. A blank and three periods (...), if used in tables, denote information that is not applicable or not available, respectively. 25. Types of outages The outage type is a three-character code. The third character is for unplanned outages only: Code_1 description:

(P) Planned outage due to causes under the plant management control (U) Unplanned outage due to causes under the plant management control (X) Outage due to causes beyond the plant management control ("external")

Code_2 description:

(F) Full outage (P) Partial outage

Code_3 description:

(1) Controlled shutdown or load reduction that could be deferred but had to be performed earlier than four weeks after the cause occurred or before the next refueling outage, whatever comes first

(2) Controlled shutdown or load reduction that had to be performed in the next 24 hours after the cause occurred

(3) Extension of planned outage (4) Reactor scram, automatic (5) Reactor scram, manual.

26. Main causes of outages

(A) Plant equipment failure (B) Refuelling without a maintenance (C) Inspection, maintenance or repair combined with refuelling (D) Inspection, maintenance or repair without refuelling (E) Testing of plant systems or components (F) Major back-fitting, refurbishment or upgrading activities with refuelling (G) Major back-fitting, refurbishment or upgrading activities without refuelling (H) Nuclear regulatory requirements (J) Grid failure or grid unavailability (K) Load-following (frequency control, reserve shutdown due to reduced

energy demand) (L) Human factor related (M) Governmental requirements or Court decisions (N) Environmental conditions (flood, storm, lightning, lack of cooling water due

to dry weather, cooling water temperature limits etc.) (P) Fire

22

(R) External restrictions on supply and services (lack of funds due to delayed payments from customers, disputes in fuel industries, fuel-rationing, labour strike outside the plant, spare part delivery problems etc.)

(S) Fuel management limitation (including high flux tilt, stretch out or coast-down operation)

(T) Offsite heat distribution system unavailability (U) Security and access control and other preventive shutdown due to external

threats (Z) Others

27. Plant systems affected

Nuclear Systems 11.00 Reactor and Accessories 11.01 Reactor vessel and main shielding (including penetrations and nozzles) 11.02 Reactor core (including fuel assemblies) 11.03 Reactor internals (including steam separators/dryers - BWR, graphite,

pressure tubes) 11.04 Auxiliary shielding and heat insulation 11.05 Moderator and auxiliaries (PHWR) 11.06 Annulus gas system (PHWR/RBMK) 11.99 None of the above systems 12.00 Reactor I&C Systems 12.01 Control and safety rods (including drives and special power supply) 12.02 Neutron monitoring (in-core and ex-core) 12.03 Reactor instrumentation (except neutron) 12.04 Reactor control system 12.05 Reactor protection system 12.06 Process computer 12.07 Reactor recirculation control (BWR) 12.99 None of the above systems 13.00 Reactor Auxiliary Systems 13.01 Primary coolant treatment and clean-up system 13.02 Chemical and volume control system 13.03 Residual heat removal system (including heat exchangers) 13.04 Component cooling system 13.05 Gaseous, liquid and solid radwaste treatment systems 13.06 Nuclear building ventilation and containment inerting system 13.07 Nuclear equipment venting and drainage system (including room floor

drainage) 13.08 Borated or refuelling water storage system 13.09 CO2 injection and storage system (GCR) 13.10 Sodium heating system (FBR) 13.11 Primary pump oil system (including RCP or make-up pump oil) 13.12 D2O leakage collection and dryer system (PHWR) 13.13 Essential auxiliary systems (GCR) 13.99 None of the above systems 14.00 Safety Systems

23

14.01 Emergency core cooling systems (including accumulators and core spray system)

14.02 High pressure safety injection and emergency poisoning system 14.03 Auxiliary and emergency feedwater system 14.04 Containment spray system (active) 14.05 Containment pressure suppression system (passive) 14.06 Containment isolation system (isolation valves, doors, locks and

penetrations) 14.07 Containment structures 14.08 Fire protection system 14.99 None of the above systems 15.00 Reactor Cooling Systems 15.01 Reactor coolant pumps/blowers and drives 15.02 Reactor coolant piping (including associated valves) 15.03 Reactor coolant safety and relief valves (including relief tank) 15.04 Reactor coolant pressure control system 15.05 Main steam piping and isolation valves (BWR) 15.99 None of the above systems 16.00 Steam generation systems 16.01 Steam generator (PWR), boiler (PHWR, AGR), steam drum vessel

(RBMK, BWR) 16.02 Steam generator blowdown system 16.03 Steam drum level control system (RBMK, BWR) 16.99 None of the above systems 17.00 Safety I&C Systems (excluding reactor I&C) 17.01 Engineered safeguard feature actuation system 17.02 Fire detection system 17.03 Containment isolation function 17.04 Main steam/feedwater isolation function 17.05 Main steam pressure emergency control system (turbine bypass and

steam dump valve control) 17.06 Failed fuel detection system (DN monitoring system for PHWR) 17.07 RCS integrity monitoring system (RBMK) 17.99 None of the above systems Fuel and Refuelling Systems 21.00 Fuel Handling and Storage Facilities 21.01 On-power refuelling machine 21.02 Fuel transfer system 21.03 Storage facilities, including treatment plant and final loading and cask

handling facilities 21.99 None of the above systems Secondary plant systems 31.00 Turbine and auxiliaries 31.01 Turbine 31.02 Moisture separator and reheater 31.03 Turbine control valves and stop valves

24

31.04 Main condenser (including vacuum system) 31.05 Turbine by-pass valves 31.06 Turbine auxiliaries (lubricating oil, gland steam, steam extraction) 31.07 Turbine control and protection system 31.99 None of the above systems 32.00 Feedwater and Main Steam System 32.01 Main steam piping and valves 32.02 Main steam safety and relief valves 32.03 Feedwater system (including feedwater tank, piping, pumps and

heaters) 32.04 Condensate system (including condensate pumps, piping and heaters) 32.05 Condensate treatment system 32.99 None of the above systems 33.00 Circulating Water System 33.01 Circulating water system (pumps and piping/ducts excluding heat sink

system) 33.02 Cooling towers / heat sink system 33.03 Emergency ultimate heat sink system 33.99 None of the above systems 34.00 Miscellaneous Systems 34.01 Compressed air (essential and non-essential / high-pressure and low-

pressure) 34.02 Gas storage, supply and cleanup systems (nitrogen, hydrogen, carbon

dioxide etc.) 34.03 Service water / process water supply system (including water

treatment) 34.04 Demineralized water supply system (including water treatment) 34.05 Auxiliary steam supply system (including boilers and pressure control

equipment) 34.06 Non-nuclear area ventilation (including main control room) 34.07 Chilled water supply system 34.08 Chemical additive injection and makeup systems 34.09 Non-nuclear equipment venting and drainage system 34.10 Communication system 34.99 None of the above systems 35.00 All other I&C Systems 35.01 Plant process monitoring systems (excluding process computer) 35.02 Leak monitoring systems 35.03 Alarm annunciation system 35.04 Plant radiation monitoring system 35.05 Plant process control systems 35.99 None of the above systems Electrical Systems 41.00 Main Generator Systems 41.01 Generator and exciter (including generator output breaker) 41.02 Sealing oil system

25

41.03 Rotor cooling gas system 41.04 Stator cooling water system 41.05 Main generator control and protection system 41.99 None of the above systems 42.00 Electrical Power Supply Systems 42.01 Main transformers 42.02 Unit self-consumption transformers (station, auxiliary, house reserve

etc.) 42.03 Vital AC and DC plant power supply systems (medium and low voltage) 42.04 Non-vital AC plant power supply system (medium and low voltage) 42.05 Emergency power generation system (e.g. emergency diesel generator

and auxiliaries) 42.06 Power supply system logics (including load shed logic, emergency bus

transfer logic, load sequencer logic, breaker trip logic etc.) 42.07 Plant switchyard equipment 42.99 None of the above systems

26

Figure 1 Nuclear Power Reactors Operating Experience

0

2000

4000

6000

8000

10000

12000

14000

1958 1963 1968 1973 1978 1983 1988 1993 1998 2003

Cum

ulat

ive

Rea

ctor

-Yea

rsThe future potentialData unavailable to the IAEAData available in IAEA PRIS

27

Figure 2 Lifetime Energy Availability Factors up to 2004(only reactors with capacity greater than 100 MW(e) and with more than one year of commercial operation)

Figure 3 Reactors with High Availability Factors(only reactors with capacity greater than 100 MW(e) and with more than one year of commercial operation)

11

35

30 0 2

3 1

21

78

93

106

62

14

00

20

40

60

80

100

120

< 30

%

30

35%

35

40%

40

45%

45

50%

50

55%

55

60%

60

65%

65

70%

70

75%

75

80%

80

85%

85

90%

90

95%

> 95

%

Energy Availability Factor Range

Nu

mb

er o

f R

eact

ors

0

20

40

60

80

100

1986 1988 1990 1992 1994 1996 1998 2000 2002 2004

% o

f R

eact

ors

70 79% 80 89% 90 100%

28

Figure 4 Average Energy Availability Factors(only reactors with capacity greater than 100 MW(e) and with more than one year of commercial operation)

7981

8283 84

81

83

7374 74

7273

74 74 7476

78 7877

0

10

20

30

40

50

60

70

80

90

100

1986 1988 1990 1992 1994 1996 1998 2000 2002 2004

Ener

gy A

vaila

bilit

y Fa

ctor

(%)

29

Figure 5 Number of Reactors in Operation (as of 1 January 2005)Note: There were 6 reactors in operation in Taiwan, China.

Figure 6 Number of Reactors by Age (as of 1 January 2005)

10459

5431

2319

1818

1514

1199

766

5444

22222

11111

0 10 20 30 40 50 60 70 80 90 100 110

USAFRANCE

JAPANRUSSIA

UKKOREA RP

CANADAGERMANYUKRAINE

INDIASWEDEN

CHINASPAIN

BELGIUMCZECH R.

SLOVAKIASWITZRLDBULGARIA

FINLANDHUNGARYARGNTINA

BRAZILMEXICO

PAKISTANS.AFRICAARMENIA

LITHNIANETHLNDS

ROMANIASLOVENIA

Number of Reactors

5

2

6

3

6

4 43

65 5

9

6

4

1011

14

22

24

3233

21

19

2221

7

1514

16

11

23

15

10

12

5

7

21

2 2

0

5

10

15

20

25

30

35

0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38

Reactor Age (years)

Num

ber o

f Rea

ctor

s

30

5. ABBREVIATIONS

COUNTRY CODES

AM ARMENIA AR ARGENTINA BE BELGIUM BG BULGARIA BR BRAZIL CA CANADA CH SWITZERLAND CN CHINA CZ CZECH REPUBLIC DE GERMANY ES SPAIN FI FINLAND FR FRANCE GB UNITED KINGDOM HU HUNGARY IN INDIA JP JAPAN KR KOREA, REPUBLIC OF KZ KAZAKHSTAN LT LITHUANIA, REPUBLIC OF MX MEXICO NL NETHERLANDS PK PAKISTAN RO ROMANIA RU RUSSIAN FEDERATION SE SWEDEN SI SLOVENIA SK SLOVAK REPUBLIC TW TAIWAN, CHINA UA UKRAINE US UNITED STATES OF AMERICA ZA SOUTH AFRICA

REACTOR TYPES

ABWR Advanced Boiling Light-Water-Cooled and Moderated Reactor AGR Advanced Gas-Cooled, Graphite-Moderated Reactor BWR Boiling Light-Water-Cooled and Moderated Reactor FBR Fast Breeder Reactor GCR Gas-Cooled, Graphite-Moderated Reactor HTGR High-Temperature Gas-Cooled, Graphite-Moderated Reactor HWGCR Heavy-Water-Moderated, Gas-Cooled Reactor HWLWR Heavy-Water-Moderated, Boiling Light-Water-Cooled Reactor LWGR Light-Water-Cooled, Graphite-Moderated Reactor PHWR Pressurized Heavy-Water-Moderated and Cooled Reactor PWR Pressurized Light-Water-Moderated and Cooled Reactor SGHWR Steam-Generating Heavy-Water Reactor WWER Water Cooled Water Moderated Power Reactor

OPERATORS

AMEREN AMEREN AMERGEN AMERGEN ENERGY CO. ANAV ASOCIACION NUCLEAR ASCO-VANDELLOS A.I.E. (ENDESA/ID) ANPP ARIZONA NUCLEAR POWER PROJECT BE BRITISH ENERGY BKAB BARSEBECK KRAFT AB BKW BKW ENERGIE AG BNFL BRITISH NUCLEAR FUELS PLC BRUCEPOW BRUCE POWER CEA/EDF COMMISSARIAT A L'ENERGIE ATOMIQUE / ELECTRICITE DE FRANCE CEZ CZECH POWER COMPANY , CEZ A.S. CFE COMISION FEDERAL DE ELECTRICIDAD CHUBU CHUBU ELECTRIC POWER CO. CHUGOKU CHUGOKU ELECTRIC POWER CO.

31

CNAT CENTRALES NUCLEARES ALMARAZ-TRILLO(ID/UFG/ENDESA/HC/NUCLENOR ) CONST CONSTELLATION NUCLEAR GROUP DETED DETROIT EDISON CO. DOMIN DOMINION VIRGINIA POWER DUKE DUKE POWER CO. EBO ELECTROSTATION BOHUNICE EDF ELECTRICITE DE FRANCE ELECTRAB ELECTRABEL M. V. NUCLEAIRE PRODUKTIE ELETRONU ELETROBRAS TERMONUCLEAR SA ELETRONUCLEAR EMO ELECTROSTATION MOCHOVCE EnBW ENBW KRAFTWERK AG ENERGYNW ENERGY NORTWEST ENTERGY ENTERGY NUCLEAR EON EON KERNKRAFT GES.M.B.H EPZ N.V. ELEKTRICITEITS-PRODUKTIEMAATSCHAPPIJ ZUID-NEDERLAND ESKOM ESKOM EXELON EXELON NUCLEAR CO. FENOC FIRST ENERGY NUCLEAR OPERATING CO. FKA FORSMARK KRAFTGRUPP AB FORTUMPH FORTUM POWER AND HEAT OY (FORMER IVO) FPL FLORIDA POWER & LIGHT CO. GNPJVC GUANDONG NUCLEAR POWER JOINT VENTURE COMPANY LIMITED(GNPJVC) HEPCO HOKKAIDO ELECTRIC POWER CO. HEW HAMBURGISCHE ELEKTRIZITAETSWERKE HOKURIKU HOKURIKU ELECTRIC POWER CO. HQ HYDRO QUEBEC ID IBERDROLA, S.A. IMPCO INDIANA MICHIGAN POWER CO. INPP IGNALINA NUCLEAR POWER PLANT JAPCO JAPAN ATOMIC POWER CO. JNC JAPAN NUCLEAR CYCLE DEVELOPEMENT INSTITUTE JSC JOINT STOCK COMPANY ARMENIA NPP KEPCO KANSAI ELECTRIC POWER CO. KHNP KOREA HYDRO AND NUCLEAR POWER CO. KKG KERNKRAFTWERK GOESGEN-DAENIKEN AG KKL KERNKRAFTWERK LEIBSTADT KYUSHU KYUSHU ELECTRIC POWER CO. LANPC LINGAO NUCLEAR POWER COMPANY LTD. NASA NUCLEOELECTRICA ARGENTINA S.A. NBEPC NEW BRUNSWICK ELECTRIC POWER COMMISSION NEC NATIONAL ELECTRICITY COMPANY, BRANCH NPP-KOZLODUY NEK NUKLEARNA ELEKTRARNA KRSKO NNEGC NATIONAL NUCLEAR ENERGY GENERATING COMPANY NOK NORDOSTSCHWEIZERISCHE KRAFTWERKE NPCIL NUCLEAR POWER CORPORATION OF INDIA LTD. NPPD NEBRASKA PUBLIC POWER DISTRICT NPQJVC NUCLEAR POWER PLANT QINSHAN JOINT VENTURE COMPANY LTD. NUCLENOR NUCLENOR, S.A. NUCMAN NUCLEAR MANAGEMENT CO. OKG OKG AKTIEBOLAG OPG ONTARIO POWER GENERATION OPPD OMAHA PUBLIC POWER DISTRICT PAEC PAKISTAN ATOMIC ENERGY COMMISSION PAKS RT. PAKS NUCLEAR POWER PLANT LTD PGE PACIFIC GAS & ELECTRIC CO. PP&L PENNSYLVANIA POWER & LIGHT CO. PROGRESS PROGRESS ENERGY CORPORATION PSEG PUBLIC SERVICE ELECTRIC & GAS CO. QNPC QINSHAN NUCLEAR POWER COMPANY RAB RINGHALS AB REA ROSENERGOATOM, CONSORTIUM RGE ROCHESTER GAS & ELECTRIC CORP. RWE RWE ENERGIE AG SCE SOUTHERN CALIFORNIA EDISON SCEG SOUTH CAROLINA ELECTRIC & GAS CO. SHIKOKU SHIKOKU ELECTRIC POWER CO. SNN SOCIETATEA NATIONALA NUCLEARELECTRICA S.A. SOUTH SOUTHERN NUCLEAR OPERATING CO. STP STP NUCLEAR OPERATING CO. TEPCO TOKYO ELECTRIC POWER CO. TOHOKU TOHOKU ELECTRIC POWER CO. TPC TAI POWER CO. TQNPC THE THIRD QINSHAN JOINTED VENTURE COMPANY LTD. TVA TENNESSEE VALLEY AUTHORITY TVO TEOLLISUUDEN VOIMA OY TXU TXU ELECTRIC CO. UFG UNION FENOSA GENERATION S.A.

32

WOLF WOLF CREEK NUCLEAR OPERATION CORP.

CONTRACTORS

AA ALSTHOM ATLANTIQUE ABBATOM ABBATOM (formerly ASEA-ATOM) ACECOWEN ACECOWEN ( ACEC-COCKERILL-WESTINGHOUSE ) ACLF (ACECOWEN - CREUSOT LOIRE - FRAMATOME) AECL ATOMIC ENERGY OF CANADA LTD. AECL/DAE ATOMIC ENERGY OF CANADA Ltda AND DEPARTMENT OF ATOMIC ENERGY(INDIA) AECL/DHI ATOMIC ENERGY OF CANADA LTD./DOOSAN HEAVY INDUSTRY & CONSTRUCTION AEE ATOMENERGOEXPORT APC ATOMIC POWER CONSTRUCTION LTD. ASEASTAL ASEA-ATOM / STAL-LAVAL B&W BABCOCK & WILCOX CO. BBC BROWN BOVERI ET CIE CE COMBUSTION ENGINEERING CO. CGE CANADIAN GENERAL ELECTRIC CNCLNEY CNIM-CONSTRUCTIONS NAVALES ET INDUSTRIELLES DE MEDITERRANEE CL -

CREUSOT LOIRE , NEY - NEYRPIC CNNC CHINA NATIONAL NUCLEAR CORPORATION DHICKAEC DOOSAN HEAVY INDUSTRIES & CONSTRUCTION CO.LTD./KOREA

ATOMICENERGY RESEARCH INSTITUTE/COMBUSTIONENGINEERING DHICKOPC DOOSAN HEAVY INDUSTRIES & CONSTRUCTION CO.LTD./KOREA

POWER ENGINEERING COMPANY/COMBUSTIONENGINEERING EE/B&W/T THE ENGLISH ELECTRIC CO. LTD / BABCOCK & WILCOX CO. /

TAYLOR WOODROW CONSTRUCTION LTD. FRAM FRAMATOME FRAMACEC FRAMACECO ( FRAMATOME-ACEC-COCKERILL ) GE GENERAL ELECTRIC COMPANY (US) GEC GENERAL ELECTRIC COMPANY (UK) GETSCO GENERAL ELECTRIC TECHNICAL SERVICES CO. HITA/GE HITACHI LTD./GENERAL ELECTRIC CO. HITACHI HITACHI LTD. KWU SIEMENS KRAFTWERK UNION AG KWU/STOR KRAFTWERK UNION AG / STORK M MITSUBISHI HEAVY INDUSTRY LTD MAEP MINATOMENERGOPROM, MINISTRY OF NUCLEAR POWER AND INDUSTRY MNE MINISTRY OF NUCLEAR ENERGY OF RUSSIAN FEDERATION NEI.P NEI PARSONS NNC NATIONAL NUCLEAR CORPORATION NPC NUCLEAR POWER CO. LTD. NPCIL NUCLEAR POWER CORPORATION OF INDIA LTD. OH/AECL ONTARIO HYDRO / ATOMIC ENERGY OF CANADA LTD. PAA PRODUCTION AMALGAMATION 'ATOMMASH', VOLGODONSK PAIP PRODUCTION AMALGAMATION IZHORSKY PLANT ATOMMASH, VOLGODONSK,

RUSSIA PPC PWR POWER PROJECTS SIEM,KWU SIEMENS AG, KRAFTWERK UNION AG SIEMENS SIEMENS AG SKODA SKODA CONCERN NUCLEAR POWER PLANT WORKS TNPG THE NUCLEAR POWER GROUP LTD. TOSHI/GE TOSHIBA CORPORATION/GENERAL ELECTRIC CO. TOSHIBA TOSHIBA CORPORATION UKAEA UNITED KINGDOM ATOMIC ENERGY AUTHORITY WEST WESTINGHOUSE ELECTRIC CORPORATION

33

6. DATA SHEETS ON INDIVIDUAL NUCLEAR POWER STATIONS UNITS

1. 2.

3.

LFOFEUFPUFUCLF

4.

5.

Design Net RUP:

EAFUCF

Mar Apr

100.0100.0

Type:Net Reference Unit Powerat the beginning of 2004:

Energy Availability Factor:

Design Discharge Burnup:

335.0 MW(e)

Production Summary 2004Energy Production: 2725.0 GW(e).h

Station DetailsPHWR

319.0 MW(e)5600 MW.d/t

Load Factor:Operating Factor:Energy Unavailability Factor:

SIEMENS (SIEMENS AG)NASA (NUCLEOELECTRICA ARGENTINA S.A.)

AR-1 ATUCHA-1Operator:Contractor:

2004 Operating Experience

GW(e).hMay Jun Jul Aug Sep Oct

0.00.0XUF

(%)(%)(%)(%)(%)(%)(%)

98.7100.0

0.00.0

Dec Annual246.0 253.4 245.1 252.4 182.8 224.4 250.9Jan

81.6 78.0 100.0

NovFeb188.3 190.4 242.9

80.8 76.4 100.7

226.2 222.181.8 76.7 100.0 100.0 100.0 100.0 72.1 91.4 99.9 93.6 90.381.8 76.7 100.0 100.0 100.0 100.0 72.1 91.5 99.9 93.6 90.3

101.7 101.6 101.3 73.3 93.0 100.7 93.8 89.1100.0 100.0 100.0 73.9 93.3 100.0 100.0 100.0

18.2 23.3 0.0 0.0 0.0 0.0 27.9 8.6 0.1 6.4 9.70.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0

27.9 8.618.2 23.3 0.0 0.0 9.70.0 0.0 0.0 0.0 0.0 0.0 0.0

0.0 0.0

7.80.0

UCLF replaces previously used UUF.

0.0 0.0 0.0 0.0(%)0.1 6.4

92.292.292.693.9

01 Jun 196813 Jan 1974

2004 Monthly Performance Data

2004 Summary of Operation

7.80.0

2725.0

Lifetime Generation:Cumulative Energy Availability Factor:

77.4%

Historical Summary

Date of Commercial Operation:

Date of First Criticality:Date of Grid Connection:

Date of Construction Start:

24 Jun 1974

92.2%92.6%93.9%7.8%

60791.2 GW(e).h71.0%68.1%

29.0%Cumulative Energy Unavailability Factor:

534 hoursTotal Offline Time:

Cumulative Load Factor:Cumulative Unit Capability Factor:

19 Mar 1974

Year

2356.0Annual Cumul. Hours OF (%)

78.4335.0 8101 92.51984

77.9 80.3 78.01983 77.9 78.4

Energy AvailabilityFactor (in %)

Load Factor (in %)Annual

Time OnlineCapacity

MW(e)Annual Cumul. Annual Cumul.

EnergyGW(e).h

Performance for Full Years of Commercial OperationUnit Capability Factor (in %)

1706.1 335.0 98.7 80.0 98.7 80.0 58.0 75.9 8678 98.81985 1470.5 335.0 91.6 81.0 91.6 81.0 50.1 73.6 7159 81.71986 2205.0 335.0 75.8 80.6 75.8 80.6 75.1 73.7 7532 86.01987 1405.8 335.0 49.2 78.2 49.2 78.2 47.9 71.7 4391 50.11988 808.1 335.0 27.1 74.5 27.1 74.5 27.5 68.5 2515 28.61989 0.0 335.0 0.0 69.5 0.0 69.5 0.0 63.9 0 0.01990 1722.6 335.0 84.9 70.5 58.7 68.8 58.7 63.6 7201 82.21991 2721.9 335.0 92.6 71.8 92.6 70.2 92.8 65.3 8390 95.81992 2230.2 335.0 76.3 72.0 76.3 70.6 75.8 65.9 7089 80.71993 2403.7 335.0 82.2 72.6 82.2 71.2 81.9 66.8 7287 83.21994 2651.9 335.0 90.4 73.5 90.4 72.1 90.4 67.9 7916 90.41995 2671.7 335.0 92.3 74.4 92.3 73.1 91.0 69.1 8376 95.61996 2038.8 335.0 70.6 74.2 70.6 73.0 69.3 69.1 6990 79.61997 2720.1 335.0 93.4 75.0 93.4 73.9 92.7 70.1 8329 95.11998 2374.4 335.0 81.4 75.3 81.3 74.2 80.9 70.5 7242 82.71999 1395.5 335.0 47.8 74.2 47.8 73.1 47.6 69.6 4364 49.82000 1677.9 335.0 72.8 74.1 56.8 72.5 57.0 69.1 5038 57.42001 1426.0 335.0 64.6 73.8 48.4 71.6 48.6 68.4 4405 50.32002 1011.5 335.0 34.6 72.4 34.6 70.3 34.5 67.2 3030 34.62003 2020.6 335.0 68.8 72.3 68.8 70.2 68.92004 2725.0 335.0 92.2 8250 93.9

67.2 6094 69.692.6 68.172.9 92.2 71.0

37

6.

7.

A.B.C.

D.

E.H.J.K.

8.

AR-1 ATUCHA-12004 Operating Experience

24 Feb 291.0 100.5

2004 OutagesDescription

UF4Date Hours GW(e).h Type Code

A42 REACTOR SCRAM AT FULL POWER OPERATION DUE TO LOSS OF OFF-SITE POWER.AREACTOR COOLANT PUMP SEAL WAS DAMAGED AND IT HAD TO BE REPLACED

22 Aug 170.0 63.0 UF4 A42 REACTOR SCRAM AT FULL POWER OPERATION.THE EMERGENCY GENERATION SIGNAL

27.0 UF2

TRIGGERED DUE TO A HYDRAULIC TURBINE DISCONNECTION AND A SYNCHRONIZATIONFAILURE OF A DIESEL

A11 CONTROLED SHUTDOWN DUE TO A LEAKAGE FROM A FUEL CHANNEL PLUG HOLDER WELD09 Nov 1260.0 39.5 UP1 S11 LOAD REDUCTION TO 92% OF FULL POWER DUE TO RADIOCHEMICAL PARAMETER30 Aug 72.0

INCREASE.THERE WERE FOUND MANY FAULT FUEL ELEMENTS

Full Outages, Analysis by Cause

Outage Cause2004 Hours Lost

1974 to 2004Average Hours Lost Per Year

Planned Unplanned External Planned Unplanned ExternalPlant equipment failure 533 802 2Refuelling without a maintenance 14Inspection, maintenance or repair 7combined with refuellingInspection, maintenance or repair 1251without refuellingTesting of plant systems or components 6Nuclear regulatory requirements 1 90Grid failure or grid unavailability 2Load-following (frequency control, 16 55reserve shutdown due to reduced energydemand)

1264 833 149Total 533 2246Subtotal 0 533 0

Equipment Related Full Outages, Analysis by System

System2004

Hours Lost1974 to 2004

Average Hours Lost Per Year11. Reactor and Accessories 72 12312. Reactor I&C Systems 5513. Reactor Auxiliary Systems 16114. Safety Systems 4115. Reactor Cooling Systems 21216. Steam generation systems 6117. Safety I&C Systems (excluding reactor I&C) 1231. Turbine and auxiliaries 1132. Feedwater and Main Steam System 2733. Circulating Water System 941. Main Generator Systems 6

Total 533 77442. Electrical Power Supply Systems 461 56

38

1. 2.

3.

LFOFEUFPUFUCLF

4.

5.

Design Net RUP:

EAFUCF

Mar Apr

100.0100.0

ON THE 04/08/04, 100.000.000 MW(E)H OF GENERATION WERE REACHED FROM THE FIRST




600.0 MW(e)


Station DetailsPHWR

600.0 MW(e)7200 MW.d/t


AECL (ATOMIC ENERGY OF CANADA LTD.)NASA (NUCLEOELECTRICA ARGENTINA S.A.)

AR-2 EMBALSEOperator:Contractor:



0.00.0XUF

(%)(%)(%)(%)(%)(%)(%)

99.0100.0

0.00.0

Dec Annual441.7 0.0 312.6 416.7 419.4 431.3 440.7Jan

100.0 100.0 93.5

NovFeb412.4 441.8 400.5

98.7 99.0 92.7

429.3 443.1100.0 99.9 92.7 0.0 72.4 93.4 94.0 99.8 99.6 99.8 99.9100.0 99.9 92.7 0.0 72.4 93.7 94.0 99.8 99.6 99.8 99.9

0.0 72.4 93.4 94.0 99.8 98.7 99.4 99.30.0 72.9 93.5 94.1 100.0 99.7 100.0 100.0

0.0 0.1 7.3 100.0 27.6 6.6 6.0 0.2 0.4 0.2 0.10.0 0.0 7.3 100.0 27.6 0.0 0.0 0.0 0.0 0.0 0.0

6.0 0.20.0 0.1 0.0 0.0 0.10.0 0.0 0.0 0.0 0.0 0.3 0.0

0.0 6.3

12.511.3


0.0 0.0 0.0 0.0(%)0.4 0.2

87.587.587.187.7

01 Apr 197413 Mar 1983



1.10.0

4589.6


78.1%

Historical Summary




20 Jan 1984

87.5%87.1%87.7%12.5%

94220.0 GW(e).h87.1%84.3%




25 Apr 1983

Year


93.4600.0 8170 93.359.4

81.6 71.9 59.91985 81.9 93.4



Time OnlineCapacity


EnergyGW(e).h


SYNCHRONIZATION TO THE NATIONAL GRID. IN 2004 THERE WERE EXTRACTED FOR SALE 4.537.837,8 CIOF COBALT 60.

1986 3061.7 600.0 67.1 77.0 66.3 76.5 58.3 5847 66.71987 4577.0 600.0 87.9 79.7 87.9 79.4 87.1 66.3 7951 90.81988 4560.6 600.0 88.8 81.5 88.8 81.3 86.5 70.3 7798 88.81989 4659.0 600.0 90.1 83.0 89.1 82.6 88.6 73.4 7804 89.11990 5000.7 600.0 96.5 84.9 95.1 84.4 95.1 76.5 8404 95.91991 4498.8 600.0 89.7 85.5 85.8 84.5 85.6 77.6 7855 89.71992 4354.0 600.0 83.4 85.3 81.6 84.2 82.6 78.2 7440 84.71993 4773.3 600.0 90.7 85.8 90.6 84.8 90.8 79.4 7956 90.81994 5157.9 600.0 98.3 86.9 97.8 86.0 98.1 81.1 8575 97.91995 3897.9 600.0 74.3 85.9 74.3 85.1 74.2 80.6 6541 74.71996 4892.0 600.0 92.8 86.4 92.8 85.6 92.8 81.5 8176 93.11997 4737.0 600.0 89.3 86.6 89.3 85.9 90.1 82.1 7821 89.31998 4555.4 600.0 86.9 86.6 86.9 86.0 86.7 82.4 7629 87.11999 5201.8 598.0 99.1 87.4 99.1 86.8 99.3 83.5 8700 99.32000 4064.5 643.0 78.2 86.8 78.1 86.2 72.0 82.8 6837 77.82001 5128.1 600.0 97.5 87.4 97.4 86.9 97.6 83.6 8564 97.82002 4385.5 600.0 84.0 87.2 83.4 86.7 83.4 83.6 7401 84.52003 5004.1 600.0 95.1 87.6 95.1 87.1 95.22004 4589.6 600.0 87.5 7704 87.7

84.1 8367 95.587.1 84.387.6 87.5 87.1

39

6.

7.

A.B.C.

D.

E.H.J.K.

8.

AR-2 EMBALSE2004 Operating Experience

29 Apr 986.0 597.3


PFDate Hours GW(e).h Type Code

28.2 UF1D PLANNED MAINTENANCEA15 LIQUID RELIEF VALVE FAILURE

16 Aug 43.0 26.0 UF2 A15 LIQUID RELIEF VALVE REPAIR22 Jul 48.0




Planned Unplanned External Planned Unplanned ExternalPlant equipment failure 91 7 276Refuelling without a maintenance 0Inspection, maintenance or repair 109combined with refuellingInspection, maintenance or repair 986 626without refuellingTesting of plant systems or components 65 1Nuclear regulatory requirements 10 2Grid failure or grid unavailability 2 21Load-following (frequency control, 3reserve shutdown due to reduced energydemand)

Subtotal 986 91 0 817 284 21Total 1077 1122


System2004


Average Hours Lost Per Year11. Reactor and Accessories 1012. Reactor I&C Systems 613. Reactor Auxiliary Systems 5015. Reactor Cooling Systems 91 1416. Steam generation systems 7817. Safety I&C Systems (excluding reactor I&C) 131. Turbine and auxiliaries 4132. Feedwater and Main Steam System 2741. Main Generator Systems 41

Total 91 27642. Electrical Power Supply Systems 8

40

1. 2.

3.

LFOFEUFPUFUCLF

4.

5.

Design Net RUP:

EAFUCF

Mar Apr

89.689.6




376.0 MW(e)


Station DetailsWWER

376.0 MW(e)28600 MW.d/t


FAEA (Federal Atomic Energy Agency)JSC (JOINT STOCK COMPANY ARMENIA NPP)

AM-19 ARMENIA-2Operator:Contractor:



2.40.0XUF

(%)(%)(%)(%)(%)(%)(%)

91.897.810.48.0

Dec Annual256.7 197.9 231.0 220.6 0.0 0.0 165.3Jan

98.9 99.9 96.1

NovFeb231.3 229.8 151.8

88.4 82.1 56.1

250.4 261.988.7 74.4 56.3 70.9 77.2 71.1 0.0 0.0 58.4 92.0 92.090.5 92.0 56.3 92.0 91.7 88.8 0.0 0.0 58.4 92.0 92.0

70.7 85.3 78.9 0.0 0.0 59.1 92.5 93.6100.0 100.0 96.9 0.0 0.0 85.3 100.0 100.0

11.3 25.6 43.7 29.1 22.8 28.9 100.0 100.0 41.6 8.0 8.08.0 8.0 41.5 8.0 8.0 8.0 100.0 100.0 40.6 8.0 8.0

0.0 0.01.5 0.0 2.2 0.0 0.01.9 17.6 0.0 21.1 14.5 17.7 0.0

0.3 3.2

35.828.8


0.0 0.0 0.0 0.0(%)1.0 0.0

64.270.366.581.2

01 Jul 197505 Jan 1980



0.96.1

2196.6


77.7%

Historical Summary




03 May 1980

64.2%66.5%81.2%35.8%

39271.5 GW(e).h63.5%56.0%




05 Jan 1980

Year


79.3408.0 7040 80.41988

79.3 73.6 73.61987 79.3 79.3



Time OnlineCapacity


EnergyGW(e).h


2254.5 376.0 73.4 76.5 73.4 76.5 68.3 71.0 6741 76.71989 671.3 376.0 99.9 84.1 99.9 84.1 20.4 54.6 1838 21.01996 2098.0 376.0 86.3 84.6 63.6 79.1 63.5 56.8 7561 86.11997 1430.0 376.0 43.4 76.5 43.4 72.1 43.4 54.2 5700 65.11998 1416.5 376.0 44.6 71.3 44.6 67.5 43.0 52.3 6408 73.21999 1890.4 376.0 57.4 69.3 57.4 66.1 57.4 53.0 6193 70.72000 1841.5 376.0 55.8 67.6 55.8 64.8 55.8 53.4 5699 64.92001 1815.4 376.0 55.1 66.3 55.1 63.8 55.1 53.6 5660 64.62002 2078.9 376.0 63.3 66.0 63.2 63.7 63.1 54.5 6961 79.52003 1997.6 376.0 63.4 65.7 60.6 63.4 60.62004 2196.6 376.0 70.3 7135 81.2

55.1 6120 69.966.5 56.066.1 64.2 63.5

41

6.

7.

A.B.C.

D.

F.

J.

8.

AM-19 ARMENIA-22004 Operating Experience

01 Jan 7135.0 219.6


PPDate Hours GW(e).h Type Code

6.8 UF5H OPERATION AT LOWER POWER 92% NNOM DUE TO NUCLEAR REGULATORY REQUIREMENTS.A42 DISCONNECTION OF AT-1 THROUGH TRANSFORMER DIFFERENTIAL PROTECTION

ACTUATION. THE AZ-III WAS ACTIVATED. THE REACTOR SCRAM WAS ACTIVATED BY31 Jan 16.0

08 Mar 25.0 2.5 XP16.3 XP1

OPERATOR, MANUALLY.K OPERATION AT LOWER POWER DUE TO GRID RESTRICTION.K OPERATION AT LOWER POWER DUE TO GRID RESTRICTION.

08 Apr 240.0 45.0 PP D DISCONNECTION OF TG-4 FOR CLEANING THE CONDENSER AND OPERATOR LIMITATION.18 Mar 40.0

20 Apr 216.0 40.5 PP27 Apr 28.0 5.9 UF5

D DISCONNECTION OF TG-4 FOR CLEANING THE CONDENSER AND OPERATOR LIMITATION.A41 DUE TO UNSTABLE GRID, DISCONNECTION OF G-4 BY SPURIOUS ACTUATING THE

ROTORS PROTECTION DUE TO OVERLOADING DROP AZ-IV GROUPS CONTROL RODS TOLOWER LEVEL. THE REACTOR SCRAM WAS ACTIVATED BY OPERATOR, MANUALLY.

07 Jun 7.0 0.8 UP2 A42 THE DISCONNECTION OF TG-3 FROM NETWORK DUE TO DIFFERENTIAL PROTECTIONACTUATION 23T, RESULTED IN OCCURRING SHORT CIRCUIT AT BUSES 6.3 KV, LEGA.

31 Jul 1574.0 585.0 PF F PLANNED UNIT OUTAGE WITH REFUELING AND MODERNIZATION.D CONTINUATION OF PLANNED UNIT OUTAGE WITHOUT REFUELING.


01 Oct 432.0 81.0 PP



Planned Unplanned External Planned Unplanned ExternalPlant equipment failure 44 63Refuelling without a maintenance 2Inspection, maintenance or repair 1014combined with refuellingInspection, maintenance or repair 93without refuellingMajor back-fitting, refurbishment or 1574upgrading activities with refuellingGrid failure or grid unavailability 14

Subtotal 1574 44 0 1107 65 14Total 1618 1186


System2004


Average Hours Lost Per Year12. Reactor I&C Systems 015. Reactor Cooling Systems 816. Steam generation systems 1117. Safety I&C Systems (excluding reactor I&C) 231. Turbine and auxiliaries 141. Main Generator Systems 28

Total 44 2342. Electrical Power Supply Systems 16 1

42

1. 2.

3.

LFOFEUFPUFUCLF

4.

5.

Design Net RUP:

EAFUCF

Mar Apr

99.8100.0

THE REFERENCE UNIT POWER IS 392.5 MWE




392.0 MW(e)


Station DetailsPWR

392.0 MW(e)33000 MW.d/t


ACECOWEN (ACECOWEN ( ACEC-COCKERILL-WESTINGHOUSE ))ELECTRAB (ELECTRABEL M. V. NUCLEAIRE PRODUKTIE)

BE-2 DOEL-1Operator:Contractor:



0.00.2XUF

(%)(%)(%)(%)(%)(%)(%)

102.8100.0

0.20.0

Dec Annual299.7 292.4 206.2 239.3 238.4 282.6 270.0Jan

100.0 99.9 100.0

NovFeb279.6 299.3 288.3

102.5 102.6 102.1

1.5 291.899.7 100.0 99.9 98.7 72.5 81.8 83.2 99.3 91.8 0.4 98.1

100.0 100.0 100.0 100.0 74.8 82.6 100.0 100.0 92.6 0.4 98.7100.2 73.0 82.1 81.8 100.1 92.6 0.5 100.0100.0 75.1 85.3 100.0 100.0 93.0 2.6 100.0

0.3 0.0 0.1 1.3 27.5 18.2 16.8 0.7 8.2 99.6 1.90.0 0.0 0.0 0.0 25.2 0.0 0.0 0.0 7.4 96.6 1.3

0.0 0.00.0 0.0 0.0 0.0 0.00.3 0.0 0.1 1.3 2.4 0.7 16.8

0.0 17.4

14.510.7


0.7 0.8 0.0 0.6(%)0.0 3.0

85.587.686.888.1

01 Jul 196918 Jul 1974



1.72.0

2989.1


77.5%

Historical Summary




15 Feb 1975

85.5%86.8%88.1%14.5%

88641.8 GW(e).h85.4%85.6%




28 Aug 1974

Year


82.1393.0 7316 83.51984

83.2 82.0 83.51983 96.7 82.1



Time OnlineCapacity


EnergyGW(e).h


3129.0 393.0 90.2 96.0 90.2 84.0 90.6 84.3 7988 90.91985 2896.3 392.0 82.4 94.7 82.4 83.8 84.3 84.3 7330 83.71986 2685.9 392.0 79.2 93.3 78.8 83.4 78.2 83.8 7040 80.41987 2928.4 400.0 85.5 92.6 85.4 83.6 83.6 83.7 7306 83.41988 2694.1 400.0 86.6 92.1 81.3 83.4 76.7 83.2 7686 87.51989 2513.1 400.0 73.6 90.8 71.9 82.6 71.7 82.4 6475 73.91990 2859.9 400.0 85.6 90.5 83.5 82.6 81.6 82.3 7380 84.21991 3061.4 400.0 89.5 90.4 89.2 83.0 87.4 82.6 7860 89.71992 2990.5 400.0 87.7 90.2 86.5 83.2 85.1 82.8 7741 88.11993 2908.9 400.0 86.0 90.0 84.4 83.3 83.0 82.8 7580 86.51994 2921.8 400.0 88.7 89.9 84.8 83.4 83.4 82.8 7635 87.21995 2791.5 392.0 82.7 89.6 81.0 83.3 81.3 82.7 7342 83.81996 3169.4 392.0 91.5 89.7 91.3 83.6 92.0 83.2 8141 92.71997 3113.8 392.0 89.0 89.6 88.9 83.9 90.7 83.5 7899 90.21998 3292.5 392.0 94.0 89.8 93.7 84.3 95.9 84.1 8277 94.51999 3196.8 392.0 92.6 89.9 91.1 84.6 93.1 84.4 8123 92.72000 3264.8 392.0 94.3 90.1 92.3 84.9 94.8 84.8 8317 94.72001 3157.6 392.0 91.4 90.2 90.5 85.1 91.9 85.1 8098 92.42002 3260.7 392.0 93.4 90.3 93.3 85.4 95.0 85.5 8308 94.82003 3024.6 392.0 90.3 90.3 86.4 85.4 88.12004 2989.1 392.0 87.5 7742 88.1

85.6 7953 90.886.8 85.690.2 85.5 85.4

43

6.

7.

A.B.C.

D.

E.H.J.K.

L.Z.

8.

BE-2 DOEL-12004 Operating Experience

02 May 17.0 1.4


XPDate Hours GW(e).h Type Code

71.1 PFK MODULATION FOR GENCO (=GRID OWNER)E14 COLD SHUTDOWN FOR THE PERFORMANCE OF PERIODIC TESTS ON THE SAFETY

INJECTION SYSTEMS.18 Jun 179.0

06 Jul 123.0 48.4 UF206 Jul 6.0 2.4 UF4

2.4 UP2

A16 SHUTDOWN FOR REPAIR A LEAKAGE PIPE STEAMGENERATOR B.L SCRAM AND SI DUE TO HIGH STEAM PRESSUREA32 POWER REDUCTION FOR EW-PUMP DUE TO HIGH BEARING TEMPERATURE.

09 Aug 49.0 XP N33 MODULATION DUE TO COOLING WATER TEMPERATURE LIMITS.17 Jul 58.0

01 Sep 190.0 1.9 XP15 Oct 348.0 1.7 XP

20.6 PF

K MODULATION FOR GENCO (=GRID OWNER)S STRETCH-OUTC REFUELING

01 Nov 678.0 266.1 PF C REFUELING OUTAGE29 Oct 52.0

29 Nov 21.0 8.4 UF330 Nov 19.0 5.8 PP

0.7 PF

L REFUELING OUTAGE EXTENSIONC STARTUP AFTER REFUELING OUTAGE - PARTIALC STARTUP AFTER REFUELING OUTAGE - FULL

01 Dec 44.0 3.5 PP C STARTUP AFTER REFUELING OUTAGE30 Nov 2.0

D31 MAINTENANCE ON THE MODULE TURBINE REGULATION


21 Dec 3.0 0.3 PP



Planned Unplanned External Planned Unplanned ExternalPlant equipment failure 123 206Refuelling without a maintenance 3Inspection, maintenance or repair 732 782combined with refuellingInspection, maintenance or repair 8without refuellingTesting of plant systems or components 179 30 1Nuclear regulatory requirements 5Grid failure or grid unavailability 7Load-following (frequency control, 27 50reserve shutdown due to reduced energydemand)Human factor related 27Others 1

847 266 7Total 1061 1120Subtotal 911 150 0


System2004


Average Hours Lost Per Year11. Reactor and Accessories 1112. Reactor I&C Systems 1314. Safety Systems 1015. Reactor Cooling Systems 1616. Steam generation systems 123 4331. Turbine and auxiliaries 7732. Feedwater and Main Steam System 2233. Circulating Water System 041. Main Generator Systems 7


44

1. 2.

3.

LFOFEUFPUFUCLF

4.

5.

Design Net RUP:

EAFUCF

Mar Apr

100.0100.0

STARTING AT 12-07-2004 THE OUTPUT CAPACITY IS CHANGED INTO 433 MW (NEW STEAMGENERATORS). THE




393.0 MW(e)


Station DetailsPWR

392.0 MW(e)33000 MW.d/t






0.00.0XUF

(%)(%)(%)(%)(%)(%)(%)

102.9100.0

0.00.0

Dec Annual300.8 55.2 0.0 182.7 283.3 307.4 323.8Jan

100.0 99.9 100.1

NovFeb281.1 300.7 277.9

102.8 102.8 98.4

317.3 321.899.9 100.0 97.1 19.0 0.0 60.2 88.7 99.0 99.8 99.5 97.099.9 100.0 100.0 22.1 0.0 60.3 97.8 100.0 100.0 99.9 97.0

18.9 0.0 56.7 87.9 98.6 100.4 101.8 99.922.3 0.0 62.1 98.4 100.0 100.0 100.0 97.6

0.1 0.0 2.9 81.0 100.0 39.8 11.3 1.0 0.2 0.5 3.00.0 0.0 0.0 77.9 100.0 39.6 0.0 0.0 0.0 0.0 2.0

2.2 0.00.1 0.0 0.0 0.0 1.10.0 0.0 2.9 3.1 0.0 0.1 9.1

0.0 0.0

19.517.8


1.0 0.2 0.4 0.0(%)0.0 0.0

80.581.981.481.7

01 Sep 197104 Aug 1975



0.31.4

2951.9


77.5%

Historical Summary




01 Dec 1975

80.5%81.4%81.7%19.5%

81507.4 GW(e).h80.2%80.4%




21 Aug 1975

Year


84.2393.0 7508 85.57341

75.5 84.5 75.51984 90.8 84.1



Time OnlineCapacity


EnergyGW(e).h


CAPACITY WAS 392.5 MWH

1985 2908.7 392.0 83.0 90.0 83.0 76.2 84.7 76.5 83.81986 2282.6 392.0 69.8 88.2 69.8 75.6 66.5 75.6 5891 67.21987 2616.4 400.0 77.8 87.3 76.8 75.7 74.7 75.5 6612 75.51988 2906.7 400.0 83.2 87.0 82.6 76.3 82.7 76.0 7408 84.31989 2479.8 400.0 71.8 85.9 70.8 75.9 70.8 75.7 6436 73.51990 1982.6 400.0 66.5 84.6 56.6 74.6 56.6 74.4 5170 59.01991 2779.8 400.0 81.2 84.4 81.0 75.0 79.3 74.7 7136 81.51992 2971.9 400.0 86.3 84.5 86.1 75.6 84.6 75.3 7617 86.71993 2949.5 400.0 85.9 84.6 85.7 76.2 84.2 75.8 7551 86.21994 2982.4 392.0 87.3 84.7 86.2 76.7 86.9 76.4 7810 89.21995 2867.5 392.0 82.9 84.6 82.7 77.0 83.5 76.7 7342 83.81996 2888.8 392.0 83.4 84.6 83.1 77.3 83.9 77.0 7390 84.11997 2935.0 392.0 87.7 84.7 84.5 77.6 85.5 77.4 7749 88.51998 3145.0 392.0 90.2 84.9 90.1 78.2 91.6 78.0 7987 91.21999 3091.7 392.0 89.6 85.1 88.9 78.6 90.0 78.5 7875 89.92000 3135.6 392.0 90.4 85.3 89.8 79.1 91.1 79.0 8022 91.32001 3150.5 392.0 90.9 85.5 90.3 79.5 91.7 79.5 8060 92.02002 3104.5 392.0 91.4 85.8 89.5 79.9 90.4 79.9 8076 92.22003 3142.6 392.0 93.1 86.0 90.1 80.2 91.52004 2951.9 413.0 81.9 7174 81.7

80.3 8184 93.481.4 80.485.9 80.5 80.2

45

6.

7.

A.B.C.

D.

E.J.K.

L.Z.

8.


13 Apr 410.0 8.2



8.9 XPS STRETCH-OUTS STRETCH-OUT

07 May 578.0 226.9 PF C REFUELING OUTAGE01 May 163.0

01 Jun 720.0 282.6 PF01 Jul 282.0 111.3 PF

16.1 PP

C REFUELING OUTAGEC REFUELING OUTAGEC STARTUP AFTER REFUELING OUTAGE

05 Aug 26.6 XP N33 MODULATION DUE TO COOLING WATER TEMPERATURE LIMITS12 Jul 89.0

06 Aug 12.0 6.9 UF503 Sep 269.0 3.1 XP

5.1 PF

A31 SCRAM DUE TO A FAILURE IN THE MODULE TURBINE REGULATIONK MODULATION FOR GENCO (= GRID OWNER)E31 TURBINE RUNBACK : TESTING

13 Dec 6.0 2.7 UF4 L41 SCRAM DUE TO UNSUFFICIENT EXITATION12 Dec 12.0




Planned Unplanned External Planned Unplanned ExternalPlant equipment failure 12 342Refuelling without a maintenance 16Inspection, maintenance or repair 1580 821combined with refuellingInspection, maintenance or repair 181without refuellingTesting of plant systems or components 12 73 15Grid failure or grid unavailability 14Load-following (frequency control, 9 12reserve shutdown due to reduced energydemand)Human factor related 6Others 0

1084 385 14Total 1610 1483Subtotal 1592 18 0


System2004


Average Hours Lost Per Year12. Reactor I&C Systems 1113. Reactor Auxiliary Systems 614. Safety Systems 1015. Reactor Cooling Systems 2816. Steam generation systems 10031. Turbine and auxiliaries 12 9732. Feedwater and Main Steam System 1941. Main Generator Systems 12


46

1. 2.

3.

LFOFEUFPUFUCLF

4.

5.

Design Net RUP:

EAFUCF

Mar Apr

100.0100.0




1006.0 MW(e)


Station DetailsPWR

890.0 MW(e)33000 MW.d/t


FRAMACEC (FRAMACECO ( FRAMATOME-ACEC-COCKERILL ))ELECTRAB (ELECTRABEL M. V. NUCLEAIRE PRODUKTIE)




0.00.0XUF

(%)(%)(%)(%)(%)(%)(%)

100.8100.0

0.00.0

Dec Annual754.5 743.9 702.4 728.4 685.4 704.0 737.4Jan

100.0 99.9 14.2

NovFeb706.4 748.7 73.5

100.9 100.0 10.2

710.1 690.2100.0 99.6 10.0 99.4 96.9 98.8 95.4 99.1 98.9 98.2 92.2100.0 100.0 10.2 99.4 100.0 100.0 95.8 99.9 99.8 100.0 93.2

99.4 97.0 97.3 91.6 97.2 98.4 98.0 92.2100.0 100.0 100.0 96.6 100.0 100.0 100.0 95.0

0.0 0.4 90.0 0.6 3.1 1.2 4.6 0.9 1.1 1.8 7.80.0 0.0 89.3 0.3 0.0 0.0 0.0 0.1 0.2 0.0 0.0

4.3 0.00.0 0.0 0.5 0.3 6.80.0 0.3 0.2 0.0 3.1 1.2 0.4

0.0 0.0

9.27.4


0.8 0.9 1.8 1.0(%)0.0 0.0

90.891.690.492.3

01 Jan 197514 Jun 1982



1.00.8

7984.8


77.9%

Historical Summary




01 Oct 1982

90.8%90.4%92.3%9.2%

159260.0 GW(e).h85.8%85.6%




23 Jun 1982

Year


100.0900.0 85.0 85.0 85.01983 100.0 85.0 7807 89.11984



Time OnlineCapacity


EnergyGW(e).h


7074.0 900.0 89.5 94.8 89.5 87.3 89.5 87.3 8084 92.01985 6496.3 900.0 82.4 90.6 82.4 85.7 82.4 85.6 7515 85.81986 6860.0 897.0 100.0 93.0 88.5 86.4 87.3 86.1 8007 91.41987 5713.2 897.0 75.7 89.5 73.5 83.8 72.7 83.4 6905 78.81988 6777.5 890.0 88.7 89.4 85.9 84.1 86.7 83.9 7875 89.71989 5774.9 900.0 82.1 88.3 73.4 82.6 73.2 82.4 7470 85.31990 6811.8 900.0 89.9 88.5 86.4 83.1 86.4 82.9 8021 91.61991 6742.9 900.0 90.0 88.7 85.8 83.4 85.5 83.2 7913 90.31992 6732.2 900.0 92.3 89.1 90.1 84.1 85.2 83.4 7778 88.51993 5377.2 900.0 69.6 87.3 65.8 82.4 68.2 82.0 6198 70.81994 7482.3 970.0 88.4 87.4 87.7 82.9 88.1 82.6 7888 90.01995 7025.1 970.0 83.4 87.1 82.6 82.9 82.7 82.6 7396 84.41996 7334.2 993.0 84.4 86.8 83.8 82.9 84.1 82.7 7447 84.81997 8108.2 1006.0 93.5 87.3 91.9 83.6 92.0 83.4 8250 94.21998 8012.6 1006.0 92.0 87.7 90.9 84.1 90.9 83.9 8171 93.31999 8231.2 1006.0 94.8 88.1 93.4 84.7 93.4 84.5 8330 95.12000 7884.9 1006.0 89.3 88.2 89.0 84.9 89.2 84.8 7892 89.82001 7993.3 1006.0 90.9 88.3 90.2 85.2 90.7 85.1 7989 91.22002 7636.6 1006.0 86.7 88.2 86.2 85.3 86.7 85.2 7647 87.32003 7870.8 1006.0 89.8 88.3 89.7 85.5 89.3 85.4 7928 90.52004 7984.8 1006.0 91.6 88.5 90.8 85.8 90.4 85.6 8104 92.3

47

6.

7.

A.B.C.

D.

E.H.K.

L.

8.


22 Mar 226.0 2.5


XP S STRETCH-OUTDate Hours GW(e).h Type Code

01 Apr 40.0 1.5 XP02 Apr 614.0 617.9 PF

3.5 UF

S STRETCH-OUTC REFUELING OUTAGEA31 TURBINE TRIP DUE TO HIGH LEVEL GESTRA (HIGH LEVEL CONDENSATE MAIN STEAM

LINE)28 Apr 4.0

28 Apr 60.0 25.9 PP02 Jun 19.3 XP

19.3 UF4

C STARTUP AFTER REFUELING OUTAGEK MODULATION FOR GENCO (=GRID OWNER)L32 SCRAM DUE TO A WRONG CONSIGNATION FEED WATER SYSTEM (LOW LEVEL REGULATION

STEAMGENERATOR)10 Aug 23.0

11 Aug 1.0 1.2 UF12 Aug 17.0 10.0 UP

5.7 XP

A31 TRIP TURBINE DUE TO HIGH LEVEL DRAIN MAIN STEAM LINES.A35 HIGH CONDUCTIVITY IN THE STEAMGENERATOR (CHEMISTRY PARAMETERS)K MODULATION FOR GENCO (= GRID OWNER)

01 Oct 278.0 6.9 XP K MODULATION FOR GENCO (=GRID OWNER)04 Sep 217.0

01 Nov 31.0 6.6 XP05 Nov 274.0 6.2 XP

25.7 UF4

K MODULATION FOR GENCO (=GRID OWNER)K MODULATION FOR GENCO ( =GRID OWNER)A32 SCRAM DUE TO FAILURE FEEDWATER ISOLATION VALVES

08 Dec 12.0 12.1 UF4 A14 SCRAM DUE TO STOP AUXILIARY FEEDWATER PUMP07 Dec 26.0




Planned Unplanned External Planned Unplanned ExternalPlant equipment failure 43 179Refuelling without a maintenance 0Inspection, maintenance or repair 614 707 2combined with refuellingInspection, maintenance or repair 9without refuellingTesting of plant systems or components 1 1Nuclear regulatory requirements 1Load-following (frequency control, 12reserve shutdown due to reduced energydemand)Human factor related 23

Subtotal 614 66 0 717 195 0Total 680 912


System2004


Average Hours Lost Per Year11. Reactor and Accessories 1312. Reactor I&C Systems 113. Reactor Auxiliary Systems 114. Safety Systems 1215. Reactor Cooling Systems 3416. Steam generation systems 6117. Safety I&C Systems (excluding reactor I&C) 2031. Turbine and auxiliaries 5 2132. Feedwater and Main Steam System 26 941. Main Generator Systems 8


48

1. 2.

3.

LFOFEUFPUFUCLF

4.

5.

Design Net RUP:

EAFUCF

Mar Apr

97.299.9




985.0 MW(e)


Station DetailsPWR

1000.0 MW(e)33000 MW.d/t






0.12.7XUF

(%)(%)(%)(%)(%)(%)(%)

97.4100.0

2.80.0

Dec Annual714.0 708.3 697.4 696.0 267.5 156.3 729.5Jan

100.0 99.9 100.0

NovFeb681.5 730.0 701.9

99.4 99.6 99.0

706.4 731.199.2 99.6 99.2 97.3 99.4 95.0 36.6 22.1 99.6 99.2 99.499.9 99.9 100.0 98.6 100.0 98.6 42.3 22.1 100.0 99.4 99.4

96.6 98.3 95.0 36.5 22.0 99.4 99.6 99.8100.0 100.0 100.0 42.7 28.5 100.0 100.0 100.0

0.8 0.4 0.8 2.7 0.6 5.0 63.4 77.9 0.4 0.8 0.60.0 0.0 0.0 0.0 0.0 0.0 57.7 53.8 0.0 0.6 0.6

0.0 24.10.1 0.1 0.0 1.4 0.00.8 0.3 0.7 1.3 0.6 3.6 5.7

0.0 1.4

13.09.4


0.0 0.4 0.2 0.0(%)0.0 0.0

87.088.486.989.3

01 Dec 197831 Mar 1985



2.21.4

7519.8


78.2%

Historical Summary




01 Jul 1985

87.0%86.9%89.3%13.0%

142218.0 GW(e).h83.1%83.0%




08 Apr 1985

Year


0.0981.0 5263 61.31986

100.0 50.8 0.01985 0.0 76.0



Time OnlineCapacity


EnergyGW(e).h


7722.9 1006.0 90.6 90.6 90.6 90.6 87.6 87.6 7973 91.01987 6809.3 1006.0 81.4 86.0 77.0 83.8 77.3 82.5 7448 85.01988 7552.0 1000.0 87.6 86.5 85.9 84.5 86.0 83.6 7784 88.61989 7445.9 1010.0 87.4 86.8 84.4 84.5 84.2 83.8 7737 88.31990 7535.8 1010.0 88.2 87.0 85.3 84.7 85.2 84.0 7790 88.91991 7425.4 1010.0 84.8 86.7 84.1 84.6 83.9 84.0 7673 87.61992 7418.6 1010.0 86.7 86.7 85.9 84.8 83.6 84.0 7481 85.21993 6980.9 1010.0 79.6 85.8 78.9 84.0 78.9 83.3 7112 81.21994 3462.7 1001.0 39.2 80.7 39.2 79.1 39.5 78.5 3637 41.51995 6769.7 1001.0 76.9 80.3 76.8 78.8 77.2 78.4 7381 84.31996 6186.8 1001.0 70.6 79.4 69.9 78.0 70.4 77.6 6565 74.71997 7548.7 1001.0 87.1 80.0 87.0 78.8 86.1 78.3 7653 87.41998 7844.0 985.0 90.0 80.8 90.0 79.6 90.9 79.3 7998 91.31999 8008.4 985.0 92.5 81.6 92.4 80.5 92.8 80.2 8150 93.02000 7992.9 985.0 92.0 82.3 92.0 81.3 92.4 81.0 8323 94.82001 8098.9 985.0 93.3 83.0 93.2 82.0 93.9 81.8 8264 94.32002 7831.9 985.0 90.6 83.4 90.4 82.5 90.8 82.3 8017 91.52003 7781.2 985.0 91.1 83.8 90.5 82.9 90.22004 7519.8 985.0 88.3 7843 89.3

82.8 8015 91.586.9 83.084.1 87.0 83.1

49

6.

7.

A.B.C.

D.

E.K.

L.

8.


01 Jan 33.0 12.1



0.9 UPK MODULATION FOR GENCO (= GRID OWNER)S12 MODULATION DUE TO NUCLEAR PARAMETERS

01 Feb 8.0 2.4 XP K MODULATION FOR GENCO (=GRID OWNER)01 Jan 6.0

30 May 35.0 10.4 UP01 Jul 744.0 26.4 XP

10.1 UP2

Z31 CLEANING CONDENSER PART A-B-C-DS STRETCH-OUTZ32 CLEANING CONDENSER

01 Aug 314.0 41.9 XP S STRETCH-OUT03 Jul 46.0

14 Aug 426.0 423.1 PF01 Sep 264.0 260.0 PF

132.0 UF3

C REFUELING OUTAGEC REFUELING OUTAGEL REFUELING OUTAGE EXTENSION

17 Sep 87.7 86.4 PF C STARTUP AFTER REFUELING OUTAGE12 Sep 134.0

21 Sep 149.0 35.1 PP21 Sep 30.0 29.7 UF2

2.9 XP

C STARTUP AFTER REFUELING OUTAGEA14 SHUTDOWN FOR REPAIR A LEAKAGE VALVEK MODULATION FOR GENCO (=GRID OWNER)

04 Nov 27.0 4.3 PP Z32 CLEANING CONDENSER09 Oct 110.0

Z32 CLEANING CONDENSER


22 Dec 21.0 4.7 PP



Planned Unplanned External Planned Unplanned ExternalPlant equipment failure 30 314Refuelling without a maintenance 1Inspection, maintenance or repair 777 827combined with refuellingInspection, maintenance or repair 34without refuellingTesting of plant systems or components 2 1Load-following (frequency control, 61reserve shutdown due to reduced energydemand)Human factor related 134

Subtotal 777 164 0 863 377 0Total 941 1240


System2004


Average Hours Lost Per Year11. Reactor and Accessories 014. Safety Systems 30 115. Reactor Cooling Systems 2216. Steam generation systems 25831. Turbine and auxiliaries 832. Feedwater and Main Steam System 1533. Circulating Water System 041. Main Generator Systems 4


50

1. 2.

3.

LFOFEUFPUFUCLF

4.

5.

Design Net RUP:

EAFUCF

Mar Apr

100.0100.0

FULL POWER DURING 2004.




962.0 MW(e)


Station DetailsPWR

870.0 MW(e)37000 MW.d/t


ACLF ((ACECOWEN - CREUSOT LOIRE - FRAMATOME))ELECTRAB (ELECTRABEL M. V. NUCLEAIRE PRODUKTIE)

BE-3 TIHANGE-1Operator:Contractor:



0.00.0XUF

(%)(%)(%)(%)(%)(%)(%)

104.0100.0

0.00.0

Dec Annual744.5 713.0 675.6 694.6 673.7 678.5 588.7Jan

25.0 11.4 100.1

NovFeb173.3 56.8 689.2

25.9 7.9 99.6

695.3 723.124.9 8.1 99.7 100.0 100.0 100.0 97.5 100.0 82.0 100.0 100.024.9 8.1 99.7 100.0 100.0 100.0 97.6 100.0 82.0 100.0 100.0

99.6 97.5 97.1 94.1 98.0 82.1 100.4 101.0100.0 100.0 100.0 98.5 100.0 81.6 100.0 100.0

75.1 91.9 0.3 0.0 0.0 0.0 2.5 0.0 18.0 0.0 0.075.1 84.2 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0

2.5 0.00.0 7.7 0.4 0.0 0.00.0 0.0 0.0 0.0 0.0 0.0 0.0

0.0 0.0

15.513.1


0.0 0.0 0.0 0.0(%)18.0 0.0

84.584.584.184.9

01 Jun 197021 Feb 1975



2.40.0

7106.5


77.5%

Historical Summary




01 Oct 1975

84.5%84.1%84.9%15.5%

191646.4 GW(e).h83.0%82.6%




07 Mar 1975

Year


76.6870.0 7135 81.41984

76.1 76.7 76.01983 92.3 76.6



Time OnlineCapacity


EnergyGW(e).h


6374.0 870.0 83.4 91.3 83.4 76.9 83.4 76.8 7774 88.51985 5979.0 870.0 90.8 91.3 81.1 77.3 78.5 77.0 8077 92.21986 4005.0 870.0 59.1 88.3 54.8 75.3 52.6 74.8 5429 62.01987 7337.0 870.0 98.5 89.2 97.6 77.1 96.3 76.6 8733 99.71988 6310.0 870.0 84.9 88.8 83.9 77.6 82.6 77.0 7520 85.61989 6508.0 870.0 88.4 88.8 87.9 78.4 85.4 77.6 7854 89.71990 6683.0 870.0 90.8 89.0 88.4 79.0 87.7 78.3 8082 92.31991 6163.0 870.0 86.7 88.8 81.0 79.2 80.9 78.5 7714 88.11992 6059.0 870.0 80.5 88.3 79.1 79.2 79.3 78.5 7807 88.91993 7317.0 870.0 99.8 89.0 96.4 80.1 96.0 79.5 8459 96.61994 6737.0 863.0 90.7 89.0 90.0 80.6 89.1 80.0 8018 91.51995 5442.0 882.0 72.9 88.2 69.9 80.1 70.4 79.5 6488 74.11996 7210.7 931.0 88.4 88.2 88.2 80.5 88.2 79.9 7823 89.11997 7942.6 962.0 95.5 88.6 94.3 81.2 94.3 80.7 8385 95.71998 7264.0 962.0 87.4 88.5 86.3 81.4 86.2 80.9 7777 88.81999 7272.0 962.0 86.9 88.5 85.5 81.6 86.3 81.2 7905 90.22000 8457.0 962.0 99.3 88.9 99.3 82.4 100.1 82.0 8782 100.02001 6969.0 962.0 91.2 89.0 82.5 82.4 82.7 82.0 7481 85.42002 7047.2 962.0 86.0 88.9 83.9 82.4 83.6 82.1 7631 87.12003 7990.4 962.0 95.5 89.2 95.1 82.9 94.82004 7106.5 962.0 84.5 7456 84.9

82.6 8552 97.684.1 82.689.0 84.5 83.0

51

6.

7.

A.C.

D.

G.

K.

L.Z.

8.

BE-3 TIHANGE-12004 Operating Experience

08 Feb 521.0 503.2


PFDate Hours GW(e).h Type Code

577.2 PFC REFUELLINGC REFUELLING

26 Mar 57.0 54.4 UF3 Z EXTENSION OF THE REFUELLING OUTAGE01 Mar 600.0

28 Mar 62.0 25.8 PP

15.2 UF4

C POWER RISE AFTER PLANNED OUTAGE FOR INSPECTION, MAINTENANCE AND REPAIRCOMBINED WITH REFUELLING.

A35 REACTOR SCRAM BY LOW LEVEL OF STEAM GENERATOR 2.12 Oct 134.0 128.8 UF4 A32 REACTOR SCRAM BY LOW LEVEL OF SG 3 (DUE TO FEEDWATERPUMP COMMAND SYSTEM14 Aug 16.0

FAILURE).




Planned Unplanned External Planned Unplanned ExternalPlant equipment failure 150 96Inspection, maintenance or repair 1121 834combined with refuellingInspection, maintenance or repair 13without refuellingMajor back-fitting, refurbishment or 10upgrading activities without refuellingLoad-following (frequency control, 5 95reserve shutdown due to reduced energydemand)Human factor related 1Others 57

847 102 105Total 1328 1054Subtotal 1121 207 0


System2004


Average Hours Lost Per Year12. Reactor I&C Systems 1014. Safety Systems 215. Reactor Cooling Systems 3016. Steam generation systems 1631. Turbine and auxiliaries 1432. Feedwater and Main Steam System 134 733. Circulating Water System 135. All other I&C Systems 1642. Electrical Power Supply Systems 12

Total 150 93XX. Miscellaneous Systems 1

52

1. 2.

3.

LFOFEUFPUFUCLF

4.

5.

Design Net RUP:

EAFUCF

Mar Apr

100.0100.0

FULL POWER DURING 2004

Type:Net Reference Unit Powerat the begi

operating experience with nuclear …€™s 500 mw(e) prototype fast breeder reactor and japan’s...

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